ML20082C356
| ML20082C356 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/31/1995 |
| From: | Wharton L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20082C359 | List: |
| References | |
| NUDOCS 9504060312 | |
| Download: ML20082C356 (7) | |
Text
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2 ye UNITED STATES
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NUCLEAR REGULATORY COMMISSION e
2 WASHINGTON, D.C. 20066-0001
.....,o UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 m
DOCKET NO. 50-483
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AMENDMENT TO FACILITY OPERATING LICENSE y
Amendment No. 97 License No. NPF-30 2'
s, 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Union Electric Company (UE, sg' the licensee) dated September 8,1994, complies with the standards
.1j and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR 1},
Chapter I; 7
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the q'
Connission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and ~
l; safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulautons; D.
The issuance of this amendment will not be inimical to the common d..
defense and security or to the health and safety of the public; and 1
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l; 2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
i sl 9504060312 950331 PDR ADOCK 05000483 P
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(2)
Technical Soecifications and Environmental Protection' Plan The Technical Specifications contained in Appendix A, as. revised '
through~ Amendment No. 97, and the Environmental Protection Plan contained in Appendix B, both of which-are attached hereto, are.
hereby incorporated into the license. UE shall operate the facility.
in accordance with the Technical Specifications and.the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance. The Technical Specifications are to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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.- Raynard Wharton, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV
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Office of Nuclear Reactor Regulation 1s}
Attachment:
Changes to the Technical Specifications j
Date of issuance: March 31, 1995 q
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ATTACHMENT T0 LICENSE AMENDMENT NO. 97 OPERATING LICENSE N0. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page, indicated by an asterisk, is also provided to maintain document completeness.
13 REMOVE INSERT s
B 3/4 9-1 B 3/4 9-1 B 3/4 9-2*
B 3/4 9-2*
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= = = -
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that: 1) the reactor will remain subcritica'l during CORE ALTERATIONS, and (2) a unif(orm
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boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. The limitation on K of no greater than 0.95 is sufficient to prevent reactor criticality dIMing refueling operations. The locking closed of the required valves during refueling operations precludes the possibility of uncontrolled boron dilution of the
,m filled portions of the Reactor Coolant System via the CVCS blending tee. This action prevents flow to the RCS of unborated water by closing all automatic flow paths from sources of unborated water. Administrative controls will limit the volume of unborated water which can be added to the refueling pool for decontamination activities in order to prevent diluting the refueling pool below the limits specified in the LCO.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses.
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3/4.9.2 INSTRUMENTATION l
The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3 /4. 9.3 DECAY TIME dM The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time j
has elapsed to allow the radioactive decay of the short-lived fission p oducts.
This decay time is consistent with the assumptions used in the fuel handling c,
accident radiological consequence and spent fuel pool thermal-hydraulic analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be' restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based 'upon the lack of containment pressurization potential while in the REFUELING MODE.
The OPERABILITY of this system ensures the containment purge penetrations will be automatically isolated upon detection of high radiation levels within containment.
The OPERABILITY of this system is required to restrict the release of radioactive materials from the containment atmosphere to the environment.
The restriction on the setpoint for GT-RE-22 and GT-RE-33 is based on a fuel handling accident inside the Containment Building with resulting damage to one J
fuel rod and subsequent release of 0.1% of the noble gas gap activity, except.,;g for 0.35 of the Kr-85 gap activity.
The setpoint concentration of SE-3 pCi/cc s
is equivalent to approximately 150 mR/hr submersion dose rate.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.
CALLAWAY - UNIT 1 B 3/4 9-1 Amendment No. 2D,54,97
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